Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation NAPK Kumar, C Li, KJ Leonard, H Bei, SJ Zinkle Acta Materialia 113, 230-244, 2016 | 530 | 2016 |
AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding J Bischoff, C Delafoy, C Vauglin, P Barberis, C Roubeyrie, D Perche, ... Nuclear Engineering and Technology 50 (2), 223-228, 2018 | 238 | 2018 |
Irradiation hardening of pure tungsten exposed to neutron irradiation X Hu, T Koyanagi, M Fukuda, NAPK Kumar, LL Snead, BD Wirth, Y Katoh Journal of Nuclear Materials 480, 235-243, 2016 | 215 | 2016 |
Intergranular δ-hydride nucleation and orientation in zirconium alloys W Qin, NAPK Kumar, JA Szpunar, J Kozinski Acta Materialia 59 (18), 7010-7021, 2011 | 100 | 2011 |
Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum T Koyanagi, NAPK Kumar, T Hwang, LM Garrison, X Hu, LL Snead, ... Journal of Nuclear Materials 490, 66-74, 2017 | 96 | 2017 |
Preferential precipitation of hydrides in textured zircaloy-4 sheets NAPK Kumar, JA Szpunar, Z He Journal of Nuclear Materials 403 (1-3), 101-107, 2010 | 92 | 2010 |
EBSD studies on microstructure and crystallographic orientation of δ-hydrides in Zircaloy-4, Zr–1% Nb and Zr–2.5% Nb NAPK Kumar, JA Szpunar Materials Science and Engineering: A 528 (21), 6366-6374, 2011 | 89 | 2011 |
Neutron irradiation response of a Co-free high entropy alloy C Li, X Hu, T Yang, NAPK Kumar, BD Wirth, SJ Zinkle Journal of Nuclear Materials 527, 151838, 2019 | 77 | 2019 |
Mechanical properties of single-crystal tungsten irradiated in a mixed spectrum fission reactor LM Garrison, Y Katoh, NAPK Kumar Journal of nuclear materials 518, 208-225, 2019 | 74 | 2019 |
Neutron energy spectrum influence on irradiation hardening and microstructural development of tungsten M Fukuda, NAPK Kumar, T Koyanagi, LM Garrison, LL Snead, Y Katoh, ... Journal of Nuclear Materials 479, 249-254, 2016 | 72 | 2016 |
Tensile deformation of 316L austenitic stainless steel using in-situ electron backscatter diffraction and crystal plasticity simulations S Sinha, JA Szpunar, NAPK Kumar, NP Gurao Materials Science and Engineering: A 637, 48-55, 2015 | 66 | 2015 |
LAMDA: irradiated-materials microscopy at Oak Ridge National Laboratory CM Parish, NAPK Kumar, LL Snead, PD Edmondson, KG Field, C Silva, ... Microscopy and Microanalysis 21 (S3), 1003-1004, 2015 | 56 | 2015 |
Roles of texture in controlling oxidation, hydrogen ingress and hydride formation in Zr alloys JA Szpunar, W Qin, H Li, NAPK Kumar Journal of Nuclear Materials 427 (1-3), 343-349, 2012 | 48 | 2012 |
Cr-coated cladding development at Framatome J Bischoff, C Delafoy, N Chaari, C Vauglin, K Buchanan, P Barberis, ... Topfuel 2018-Light Water Reactor (LWR) Fuel Performance Meeting 2018, 2018 | 40 | 2018 |
Microstructural criteria for abrupt ductile-to-brittle transition induced by δ-hydrides in zirconium alloys W Qin, JA Szpunar, NAPK Kumar, J Kozinski Acta materialia 81, 219-229, 2014 | 40 | 2014 |
Microstructural studies and crystallographic orientation of different zones and δ-hydrides in resistance welded Zircaloy-4 sheets NAPK Kumar, JA Szpunar, Z He Journal of Nuclear materials 414 (3), 341-351, 2011 | 31 | 2011 |
High temperature oxidation response of Al/Ce doped Mo–Si–B composites J Das, B Roy, NK Kumar, R Mitra Intermetallics 83, 101-109, 2017 | 29 | 2017 |
Morphological characterization of the polyflux 210h hemodialysis filter pores A Hedayat, J Szpunar, NAP Kumar, R Peace, H Elmoselhi, A Shoker International journal of nephrology 2012, 2012 | 28 | 2012 |
Benefits of Framatome’s E-ATF evolutionary solution: Cr-coated cladding with Cr2O3-doped fuel C Delafoy, J Bischoff, J Larocque, P Attal, L Gerken, K Nimishakavi Proceedings of the TopFuel, 1-11, 2018 | 19 | 2018 |
The role of microstructure on the optical performance of neutron irradiated dielectric mirrors KJ Leonard, GE Jellison, NAPK Kumar, LL Snead Journal of nuclear materials 445 (1-3), 281-290, 2014 | 10 | 2014 |